ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Wei-Wu Chao, Jay F. Kunze, Weimin Dai, Sudarshan K. Loyalka
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 261-270
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34927
Articles are hosted by Taylor and Francis Online.
Research reactors present a different set of operating conditions than do light water (power) reactors (LWRs). Thermal-hydraulic transient/safety codes, such as the Reactor Loss of Coolant Analysis Program (RELAP), have been verified against experimental data from several test facilities designed for the operating conditions of LWRs. However, the operating pressures, temperatures, fuel type, and flow direction are quite different in most high-power research reactors. Furthermore, the coolant (water) in these reactors generally is not degasified and hence contains dissolved air. Results are given of benchmark experiments compared with RELAP predictions for the conditions encountered during a loss-of-coolant accident for a typical research reactor.